ML17285A871

LER 89-042-00:on 891106,pressure Switch,Which Provides Input to Logic Calibr,Outside Tech Spec Limits.Caused by Inadequate Procedures W/Ambiguous Instructions.Surveillance Procedures revised.W/891128 Ltr

ML17285A871
Person / Time
Site:	Columbia
Issue date:	11/28/1989
From:	Fies C, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-042, LER-89-42, NUDOCS 8912080128
Download: ML17285A871 (7)

Text

ACCELERATED DISTPJBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8912080128 DOC.DATE: 89/11/28 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FIES,C.L. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION SUBZECT: LER 89-042-00:on 891106,ADS backup nitrogen supply pressure switch calibrated outside Tech Spec limits, W/ 8 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR (ENCL I SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES

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A RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 SAMWORTH,R 1 1 D INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 S, AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1 .NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DET/ESGB 8D 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SPLB8Dl 1 1 NRRJ+S~ XB 8E 1 1' NUDOCS-ABSTRACT 1 1 aXG~ 1 RES/DSIR/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL EG&G WILLIAMSE S 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 R NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 D

S A

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE ImCUMEN1'ONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISHUBUTION LISTS FOR DOCUMENIS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES'EQUIRED: LTTR 38 ENCL 38

0 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 November 28, 1989 Docket No. 50-397 Document Control Desk .

U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.89-042

Dear Sir:

Transmitted herewith is Licensee Event Report No.89-042 for the MNP-2 Plant.

This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.

Very truly yours, Ot"tie- <<~

C. H. Powers (N/D 927M)

NNP-2 Plant Manager CNP:lr

Enclosure:

Licensee Event Report No.89-042 cc: Nr. John B. Martin, NRC Region V Nr. C. J. Bosted, NRC Site (H/D 901A)

INPO Records Center Atlanta, GA Ns. Dottie Sherman, ANI Nr. D. L. Williams, BPA (H/D 399)

OPOi-8:g&li2"::

F'LIR ADOCK 0-0003+7 PDC t $

NAC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (64) 9) APPAOVEO OMB NO, 31504104 EXPIRES: 4130/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS, FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (I) DOCKET NUMBER (2) PAGE 3 Washin ton Nuclear Plant - Unit 2

'"" '" Automatic Depressurizat>on System 0 5 0 0 03 97'FO ac up N> trogen upp y Pressure Switch Calibrated Outside Technical. Specification Limits EVENT DATE ISI LER NUMBER (6). AEIIORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR terr sf ovf NTIAL YEAR FACILITY NAMES DOCKET NUMBER(S)

NVMSE R Rj'Q'I:I NUMBER MONTH DAY 0 5 0 0 0 1 106 8 9 042 00 11 28 8 9 0 5 0 0 0 THIS REPORT IS SUBMIT'TED PUASUANT TO THE RLQVIREMENTS OF 10 CFR (); IChrch onr or mori Of thr folrorvrnp) (11)

OIIERATING MODE (9) 20.402(h) 1 20A05(c) 50.73( ~ l(2)(iv) 73.71(II)

POWER 20A05lcl(1 l(i) 50.36(c(II) 60.73( ~ l(2)(vl 73.71(cl LEVEL g g 20.405(r l(1) (iil 50.35(cl(2) 60.73( ~ I(2) lvii) OTHER ISprcify in Ahttrrct Orlovv md In Trit, IYIIC Form 20.405( ~ I (1 I (ill) 50.73( ~ l(2) II) 60.73(cl(2 I(vill)(A) 366AI 20.406( ~ I(1) (iv) 60.73( ~ l(2)(ii) 50.73( ~ l(2)(viii)(6) 20.405( ~ l(1)(vl 50.7 3 I ~ l(2)(iiil 50.73 I ~ ) (2)(nl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE C. L. Fies Com liance En ineer 50 937 7- 50 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOAT (13) X T 2 0 3 CAUSE SYSTEM COMPONENT MANUFAC MANUFAC. EPORTABLE TV RE R TVRER TO NPADS SUPPLEMENTAL REPORT EXPECTED (14I MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)

YES (if yrr, complrtr EXPECTED SUBMISSION DA TEI X NO ABSTRACT ILimlt to )400 tprcrt, i.r.. rpprovimrtrly fiftrrn tinplr tprci typrvvrrttrn linn) (16)

On'November 6, 1989 a reportability evaluation was approved which directed that an event discovered on August 13, 1989 be, reported per 10CFR50.73. The evaluation, which was ongoing during September and October, concluded a pressure switch (CIA-PS-22B) which provides input to the logic which controls the backup nitrogen supply to the Automatic Depressurization System (ADS) was calibrated incorrectly.

During the calibration, on July ll, 131.4 psig while the technical specification limit calls for a value greater than 1989, the pressure switch was set to .actuate at 135 psig on decreasing pressure. The plant operated until the next channel func-tional test (August 13, 1989) when the out of calibration condition was discovered.

Immediate corrective action was taken to calibrate CIA-PS-22B 'correctly and to investigate the cause of the out of calibration condition.

The root cause of this event was less than adequate procedures with ambiguous instructions.

Further corrective action included a modification to the surveillance procedures to emphasize the decreasing pressure trip.

The event posed no threat to the health and safety of either the public or plant personnel since the ADS'system would have been able to perform'ts safety function with the instrument slightly out of calibration.

NRC Form 366 (64)9)

NRC IORM 366A U.S, NUCLEAR REGULATORY COMMISSION (669) APPROVED OMB NO. 31500(04 EXPIRES: 4/30/92 ESTIP%KD BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVEN EPORT (LER) INFORMATION COLLECTION REQUEST: 500 HRS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO 11(E PAPERWORK REDUCTION PROJECT (3)504)104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

$/91 SEQUENTIAL rrrTlS REVISION NVMS SR NVMSSR Washin ton Nuclear Plant - Unit 2 397 89' 0 2 0 0 OF 0 4 TEXT /I/moro 4/>>or /4 rrr)rr/rrd, lr>> rddrrr'oor/NRC %%drrrr 366AM (IT)

Pl ant Condi ti ons a) Power Level - 99%

b) Plant Node - 1 Event Descri tion On November 6, 1989 a reportability evaluation was approved which directed that an event discovered on August 13,, 1989 be reported per 10CFR50.73. The reportability evaluation process for this event deemed the event not reportable in September but, upon further study in October, concluded it was reportable based on verbatim com-This event was initially discovered on pliance with the Technical Specifications.

August 13, 1989 when Plant Instrumentation and Control ( I & C) Technicians wrote a Problem Evaluation Report (PER) which documented the fact that pressure switch CIA-PS-22B was found outside the Plant Technical Specification limit. This switch provides input to the logic which controls the backup nitrogen supply to the Auto-matic Depressurization System (ADS). The ADS is part of the- Emergency Core Cooling System (ECCS) and is designed to depressurize the primary system to allow for core cooling by the low pressure ECCS systems. The "as found" trip value for CIA-PS-22B was 129 psig and the reset was 136.0 psig. The technical specification limit calls for a trip value greater than 135 psig on decreasing pressure.

The Plant System Engineer reviewed the PER 'and the results of the previous channel calibration which was performed on July 11, 1989. On the latter date pressure switch (CIA-PS-22B) was calibrated per the requirements of surveillance procedure PPN 7.4. 5.1.21, ADS - Accumulator Backup Low Pressure Alarm Div I I - Channel Func-tional Test(CFT)/Cnannel Calibration(CC). During the calibration, the Plant Instru-mentation and Control ( I&C) Technician recorded an "as left" reset value of 131.4 psig and an "as left" trip value of 137 psig. Since this is a pressure decreasing trip, the trip value should be lower than the reset value. This result was reviewed by the I & C Engineers without detection on July 14, 1989. The System Engineer con-cluded, after review on August 13, 1989, that the I & C Technician had reversed the numbers and the actual "as left" trip value for -the July ll calibration was 131.4 psig and the "as left" reset value was 137 psig.

Immediate Corrective Action Immediate corrective action was taken to calibrate CIA-PS-22B correctly on August 13, 1989 Further Evaluation and Corrective Action A. Further Evaluation

1. This event is being reported as a "....deviation from the Plant's Tech-nical Specifications...." per the requirements of 10CFR50.73(a)(2)(i)(C).

Specifically, CIA-PS-22B was inoperable between July 11, 1989 and August 13, 1989 by the Technical Specification definition and the action statement for restoration to operable status was exceeded.

NRC Form 366A (64)9)

NRC FOAM 366A U.S. NUCLEAR REGULATORY COMMISSION (64)9) APPROVED OMB NO. 31500')04 EXPIRES: 4i30i92 LICENSEE EVEN PORT (LER) ESTI~D BUADEN PEA RESPONSE TO COMPLY WTH THIS INFOAMATION COLLECTION AEQUESTI 50.0 HAS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP.530), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEDUENTIAL REVISION j$CY NUMBER NUM 8EII Mashin ton Nuclear Plant - Unit 2 o s o o o 9 7 8 90 4 2 0 0 0 3 OF 0 4 TEXT (lfmrsrs spsssis rsqrrirsd, Irss sddiddIMI AIRC Form 366A'sI ()7)

I

2. There were no structures, components or systems that were inoperable prior to the start of this event which contributed to the event.

3. The root cause of this event was less than adequate procedures with ambig-

=

uous instructions. The surveillance procedures did not specify that the signal tripped on decreasing pressure. This caused the I & C Technician to reverse the "as left" trip and reset numbers taken during the July ll, 1989 surveillance; B. Further Corrective Action

1. Further corrective 'action included a modification to surveillance proce-dures 7.4.5.1.20 and 7.4.5.1.21, ADS-Accumulator Backup Low Pressure Alarm Divisions I and II - CFT/CC. The procedures were modified to note the decreasing nature of the pressure trip.

2. Other surveillance procedures will be reviewed and modified, if. appro-priate,'o indicate the decreasing nature of the trip.

3. I & C personnel have been counseled on the need for caution when working with a signal which causes a trip on decreasing signal.

Safet Si nificance During normal operation the nitrogen supply to the ADS accumulators is the 11,000 gallon (1 million scf) cyrogenic tank which is also used to inert the primary con-tainme'nt. If this normal nitrogen supply fails, the nitrogen backup system is automatically placed into service. Three signals in two channels (A and B) are used to ini tiate the nitrogen backup for the ADS. They include CIA-PS-22A(B) 135 PSIG, CIA-PS-21A(B) 140 PSIG and CIA-V-39A(B) closed. These signals feed a two out of three logic circuit in each channel which initiates the stepping programmers for the nitrogen bottles. Programmer HA", CIA-PROG-lA, is initiated by the HAH logic and provides backup nitrogen to three ADS valves. Programmer HB", CIA-PROG-lB, is ini-tiated by the HBH logic and provides backup nitrogen to the four remaining ADS valves. The slightly lower pressure setting on CIA-PS-22B would have no impact on the HAH valves. The impact on the HBH side would have been a slight delay in the initiation of the "BH programmer if it did not get actuated by CIA-PS-21B 140 psig and CIA-V-39B closed. Specifically, the delay would have been the time needed for the pressure to drop from -the required value of 135 psig to the as found value of 129 psig. This is above the minimum pressure required to operate the ADS valves under accident conditions. In addition, the backup nitrogen subsystem was not required during the period of miscalibration. Consequently, this event posed no threat to the health and safety of either the public or plant personnel.

NRC Form 366A (64)9)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (64)9)', APPROVED OMB NO.3)S04)104 EXPIRES: 4/30/92 LICENSEE EVEN EPORT (LER) ESTI~O BURDEN PER RESPONSE TO COMPLY WTH THIS

• INFORMATION COLLECTION REQUESTI 60.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P.530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO 1HE PAPE'RWORK REDUCTION PRO/ECT (31604)104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

'YEAR  :@+ SEOUENTIAL NUMBER FN

" REVISION

,(. NUMSER

- 0' a i 0 0 0 3 9 7 0 4 0 OF TEXT /I/mare 4/reoe/s>>r/Ir/rrrd, a>> odd/dane/NRC Farm36543/(17)

Similiar Events None EIIS Information Text Reference EIIS Reference System ~tom onent Automatic Depressurization System (ADS) BG CIS-PS-22B LD PS C I S-PS-22A L'D, PS C IS-PS-21A LD PS

, CI S-PS-21B LD -

PS CIS-V-39A LD V CIS-V-398 LD V CIA-PROG-1A LD PMC C I A-P ROG'-1 B LD PMC NRC Form 366A (64)9)